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    STP484

    Irradiation Effects on Structural Alloys for Nuclear Reactor Applications

    Bement AL
    Published: 1970


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    The Symposium on Irradiation Effects on Structural Alloys for Nuclear Reactor Applications was presented at Niagara Falls, Canada, 29 June-1 July 1970, in conjunction with the Seventy-third Annual Meeting of the American Society for Testing and Materials held in Toronto, Ontario, Canada, 22-26 June 1970. The symposium was sponsored by ASTM Committee E10 on Radiosotopes and Radiation Effects. A. L. Bement, Jr., Battelle Memorial Institute, Pacific Northwest Laboratory, served as chairman of the symposium committee, which consisted of J. Moteff, cochairman, and K. M. Zwilsky, C. J. Baroch, E. Landerman, and L. E. Steele. The six sessions were presided over by L. J. Chockie, D. R. Harries, W. R. Thomas, R. Bullough, J. Moteff, and H. Bohm. Two agenda discussion sessions also were presented to survey the status of two contemporary problem areas.


    Table of Contents

    Introduction

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    How Do We Solve the Void Problem?

    Discussion

    Discussion

    Discussion

    Discussion

    Neutron Dosimetry for Reactor Pressure Vessel Applications

    Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels

    The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessel Steels

    Evaluation of the Embrittlement of Pressure Vessel Steels Irradiated in JPDR

    Demonstration of Improved Radiation Embrittlement Resistance of A533B Steel Through Control of Selected Residual Elements

    Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen

    The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Quenched and Tempered Steels

    Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels

    Effects of Irradiation in a Thermal Reactor on the Tensile Properties of Zircaloy 2 and 4 and Borated Stainless Steel

    Influence of Irradiation Temperature on the Tensile Properties of Stainless Steel

    The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests

    Metallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions

    The Temperature and Neutron Dose Dependence of Irradiation Growth in Zircaloy 2

    Quantitative Transmission Electron Microscopy of Bubbles in A1 and A1-A12O3 Alloys

    The Mechanism and Kinetics of Void Growth During Neutron Irradiation

    Void Formation in Proton Irradiated Stainless Steel

    Considerations of Metal Swelling and Related Phenomena Caused by Fast Neutron Irradiation

    Some Observations on the Structure and Tensile Properties of AISI Type 316 Steel as a Function of Fast Reactor Irradiation Temperature

    Neutron Dosimetry for Fast Reactor Applications

    Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components

    Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures

    Effect of Fast Neutron Irradiation on the Creep Rupture Properties of Type 304 Stainless Steel at 600 C

    Uniaxial and Biaxial Creep Rupture of Type 316 Stainless Steel After Fast Reactor Irradiation

    Effect of Irradiation on the Mechanical Properties of 19-9DL Alloy

    Influence of Neutron Irradiation on the Creep Rupture Properties of a 16Cr-13Ni Steel

    The Effects of Helium on the High-Temperature Ductility of Sandvik 12R72HV and Inco IN-744X

    Correlation Between the Mechanical Properties and Microstructure of Irradiated Iron and Low-Carbon Steel

    Irradiation Effects at Cryogenic Temperature on Tensile Properties of Titanium and Titanium-Base Alloys


    Committee: E10

    DOI: 10.1520/STP484-EB

    ISBN-EB: 978-0-8031-4593-1

    ISBN-13: 978-0-8031-0014-5

    ASTM International is a member of CrossRef.

    0-8031-0014-0
    978-0-8031-0014-5
    STP484-EB